////////////////////////////////////////////////////////////////////////////////////////////////////
2020/12/03 (Version 1.03.006 -> 1.03.007)
If spin (J) and parity (pi) are zero, the size of complex matrix becomes zero and calculation of inverse matrix function (zsytrf_ in "ReconResonance/RmatrixLimited/rml/Cohrent.cpp") is aborted.
To avoid this problem, parity is modified to 1 if spin and parity are zero.
////////////////////////////////////////////////////////////////////////////////////////////////////
2020/12/01 (Version 1.03.005 -> 1.03.006)
The suffix number of meta-stable nuclide is modified to distinguish grand-state and meta-stable nuclides.
The suffix number of meta-stable nuclide is add (300 + meta-stable number * 100).
For example, suffix number of Am-242 is 95242 and that of Am-242m is 95642.
(If Am-242m2 is exist, suffix number of Am-242m2 is 95742.)
Calculation of statistical error function in each ladder number is added.
(But this function is used only for debug and commented out.)
////////////////////////////////////////////////////////////////////////////////////////////////////
2020/10/28 (Version 1.03.004 -> 1.03.005)
The Bootstrap class is newly added to calculate statistical error using bootstrap and jack-knife methods.
The statistical calculation of the probability table is added in ProbabilityTableCalculator class.
The statistical error can be used as the criteria of the probability table generation.
The old version does not appropriately read the data when the number of comment line is 1 and there is bracketdata, i.e., () or [], in this comment line.
For example, if user set the comment line "U-235 (J40)", the old version of FRENDY considers that U-235 is comment data and J40 is the parameter.
The StringUtils class is modified to appropriately treat bracket data.
These files are modified to compile using Visual studio 2019.
The cross section data is often used to plot or comparison.
The xs_only function is newly added in these parser classes to reduce the reading time of the PENDF file.
////////////////////////////////////////////////////////////////////////////////////////////////////
2020/10/15 (Version 1.03.003 -> 1.03.004)
These classes are modified to treat the ACE format version 2.0.1 which is used in the ENDF/B-VIII.0 official library.
The ENDF/B-VII.1 official library uses Ver. 2.0.0 and the ENDF/B-VIII.0 official library uses Ver. 2.0.1.
PHITS and old MCNP cannot treat such new ACE format.
These offical library set old format as the comment line of new format.
The format version is modified from the new version to old version to treat PHITS and old MCNP.
The character number of nuclear name and suffix id is 10.
The new ACE format allows longer suffix id and nuclear name.
The character number is modified to 24 when the new format is used.
The old version cannot perturb the total reaction (not only probability table but also cross section).
This problem is modified and new version appropriately treats the total reaction.
////////////////////////////////////////////////////////////////////////////////////////////////////
2020/09/29 (Version 1.03.002 -> 1.03.003)
The modification of read module in Ver. 1.03.002 is inappropriate.
We removed this modification.
The PerturbNuclearData class is modified to treat MT=19.
////////////////////////////////////////////////////////////////////////////////////////////////////
2020/09/25 (Version 1.03.001 -> 1.03.002)
The bug of FastAceDataGenerator class is modified.
Print option of ACER module (iprint) is considered as the ACE output type (ascii/binary).
The ACE output type is changed from iprint to itype.
The read and write module of angular distribution (angular_distr_cos_data) is modified when angular_distr_pointer is less than 0, i.e., old cumulative angle distributions are used.
The bag of unify_energy_grid function is modified.
(The old version do not resize nbt_e.)
////////////////////////////////////////////////////////////////////////////////////////////////////
2020/09/24 (Version 1.02.031 -> 1.03.001)
The version number of FRENDY is modified to release new version of FRENDY.
////////////////////////////////////////////////////////////////////////////////////////////////////
2020/09/23 (Version 1.02.030 -> 1.02.031)
The old version considered that S-ESZ + 2NE = sigma-a is capture cross section (MT=102).
S-ESZ + 2NE = sigma-a is total neutron disappearance cross section (MT=101).
The output function of this class (get_xs_data) is modified.
Calculation of flag of inelastic scattering and absorption (iinel and iabso in PURR module) is modified.
The calculation method of old version is identical to NJOY99.
The calculation method of new version is identical to NJOY2016.
This modification affects the cross section of n-017_Cl_036.endf from ENDF/B-VIII.0 in the unresolved resonance region.
The set of energy grid of the probability table generation is modified.
The number of energy grid using new version is slightly larger than the old version.
The condition of middle energy grid addition is modified.
The new version compares the distance from E[i-1] to E[i] and from E[i] to E[i+1].
If the energy distance between E[i-1] and E[i] is greatly larger or greatly smaller than that between E[i] and E[i+1], the new version adds the middle energy grid.
The old version skips all data in the UNR blok which contains unresolved resonance range probability tables when the probability table comparison is skipped.
The new version compares the energy grid and parameter of the probability table even if the probability table comparison is skipped.
The bug of FRENDY Version 1.02.029 is found.
This version does not calculate the cross section at the unresolve resonance region.
////////////////////////////////////////////////////////////////////////////////////////////////////
2020/09/10 (Version 1.02.029 -> 1.02.030)
The warning message is modified to use ErrorManager class.
I found some bugs in the reading cross section data function and calculation of the bondarenko cross section function.
The previous version only modify the cross section which the inciden energy is unresolved resonance region.
These bugs are fixed.
These bugs are only affected from Version 1.02.013 to Version 1.02.029.
The output of header file is modified.
This modification is only affect new format.
////////////////////////////////////////////////////////////////////////////////////////////////////
2020/09/10 (Version 1.02.029 -> 1.02.030)
The previous version only output error message when there is no input file.
The new version outputs the version of FRENDY to easily check the version of FRENDY.
The calculation function of bondarenko cross section using probability table and output function
of cross section data are newly implemented.
////////////////////////////////////////////////////////////////////////////////////////////////////
2020/09/08 (Version 1.02.028 -> 1.02.029)
Calculation function of potential cross section for multi-group cross section library
generation is implemented.
Calculation function of MT=103-107 is implemented.
This function adds MT=103-107 in the PENDF file.
Since MT=103-107 is newly added in PENDF file, the calculation of gas production cross section
is also modified to treat such new MT numbers.
The transform from real value "a" to integer value "b" is modified from
"b=static_cast(a)"
to
"b=static_cast(round(a))"
to correctly transform real value.
////////////////////////////////////////////////////////////////////////////////////////////////////
2020/09/04 (Version 1.02.027 -> 1.02.028)
The calculation of total cross section at calc_probability_and_bondarenko_table_data module
which is added in Version 1.02.021 is inappropriate.
The calculation of total cross section is removed.
////////////////////////////////////////////////////////////////////////////////////////////////////
2020/09/02 (Version 1.02.026 -> 1.02.027)
Checker function of ielas option is added in ACE file generator module.
Using this function, user can easily found the input miss of ielas option.
////////////////////////////////////////////////////////////////////////////////////////////////////
2020/08/27 (Version 1.02.025 -> 1.02.026)
We found that the total probability table re-calculation scheme which is set in Ver.1.02.021 is not correct.
This function is removed.
////////////////////////////////////////////////////////////////////////////////////////////////////
2020/08/25 (Version 1.02.024 -> 1.02.025)
The modification of cross section is to avoid inappropriate P1-total bondarenko table.
The modification of cross section may affect the other parameters discribed in Version 1.02.024.
The new version only modify the cross section which is uses in P1-total bondarenko table calculation.
The modification of the cross section does not affect the other parameters.
////////////////////////////////////////////////////////////////////////////////////////////////////
2020/08/25 (Version 1.02.023 -> 1.02.024)
If the comment area is so narrow, e.g., "temp /* [K] */ 300.0", old version cannot remove comment data.
To avoid this problem, CommentRemover class is modified.
The warning message is modified.
The calculation method of bondarenko table is modified from probability table to direct sampling.
(The new calculation method is identical to NJOY2016.53.)
When the sigma0 is small, e.g., less than 100, the bondarenko table in MF=2, MT=152 is different to the NJOY result.
The cause of this difference is modification of the cross section.
FRENDY modify the cross section to infinite dilution cross-section x 1.0E-2 if the cross section is less than infinite dilution cross-section x 1.0E-2.
This modification is utilized to avoid inappropriate P1-self shielding.
We checked Ba-132 from JENDL-4.0 to set appropriate modification parameter (min_xs_coef) and it is modified from 1.0E-2 to 1.0E-4.
////////////////////////////////////////////////////////////////////////////////////////////////////
2020/08/17 (Version 1.02.022 -> 1.02.023)
Version 1.02.021 set total cross section boundary before FRENDY modifies total cross section to remove minus cross section.
In this case, probability table and its cross section becomes zero where the minus cross section is observed.
To avoid zero probability, total cross section boundary calculation function is modified.
////////////////////////////////////////////////////////////////////////////////////////////////////
2020/08/17 (Version 1.02.021 -> 1.02.022)
The old version does not add the middle energy grid where the energy grid is close to the top of Doppler broadening.
If the difference of the cross section between resolved and unresolved region, e.g., Ba-132 from JENDL-4.0, the old version cannot treat the variation of the doppler broadened cross section near the top of Doppler broadening.
////////////////////////////////////////////////////////////////////////////////////////////////////
2020/08/11 (Version 1.02.020 -> 1.02.021)
The order of reader and perturbation classes is modified from [ene_no][bin_no][xs_type_no] to [ene_no][xs_type_no][bin_no].
The ACE format order of the probability table is [ene_no][xs_type_no][bin_no].
However, the order of reader and perturbation classes is [ene_no][bin_no][xs_type_no].
The writer class does not check the order of the probability table.
The previous version cannot write probability table in the ACE file when user read ACE file using FRENDY.
The new version output runtime error when the order of the probability table is not [ene_no][xs_type_no].
The previous version modified probability table to 0.0 when the probability table is less than 0.0.
The new version modified probability table to min_sig_val (1.0E-40) since 0.0 cannot be treated when the log-log interpolation is used.
The total probability table is recalcualted in ProbabilityTableCalculator and FastAceDataGenerator classes using elastic scattering, fission and radiation probability tables.
////////////////////////////////////////////////////////////////////////////////////////////////////
2020/07/29 (Version 1.02.019 -> 1.02.020)
Warning message of these classes are modified.
The minus probability table is modified to 0.0.
////////////////////////////////////////////////////////////////////////////////////////////////////
2020/07/01 (Version 1.02.018 -> 1.02.019)
Warning message of ThermalScatterAceDataGenerator class is modified.
The principal atom number of default value is modified to correctly process thermal scattering law data.
////////////////////////////////////////////////////////////////////////////////////////////////////
2020/06/29 (Version 1.02.017 -> 1.02.018)
If the background cross section is large and the sign of it is minus, the cross section becomes minus at the valley of resonance.
In this case, the cross section at 1st or 2nd probability bin becomes minus value.
The cross section calculation is modified to be 0.0 barn when the sum of cross section and the background cross section is smaller than the min_sig_val.
This modification affects n-048_Cd_106.endf from ENDF/B-VII.0.
The treatment of narrow angular distribution implemented in Version 1.02.017 is modified.
////////////////////////////////////////////////////////////////////////////////////////////////////
2020/06/25 (Version 1.02.016 -> 1.02.017)
If the angular distribution is anisotropical, the distance of angular becomes so narrow and calculation of integrated cross section becomes infinite.
To avoid this problem, angular distance check function is added.
////////////////////////////////////////////////////////////////////////////////////////////////////
2020/06/24 (Version 1.02.015 -> 1.02.016)
To verify processing results, the processing result (incoherent inelastic scattering cross section) at the upper energy limit is compared to the elastic scattering cross section of original nucleus.
If the relative difference is larger than 10%, warning message is output.
If iwt/weight_option is 2 and the secondary energy distance is so narrow (i.e., the distance becomes 0.0 due to rounding error), MCNP6.1 is stopped with abnormal termination.
To avoid the abnormal termination of MCNP6.1, such narrow energy distribution is removed when FRENDY generates ACE files.
The minimum energy distance of the old version is 1.0E-17 MeV (1.0E-11 eV) and that of the new version is 1.0E-14 MeV (1.0E-8 eV).
The warning message of nuclear data file is removed in the default option to emphasize the warning message of nuclear data processing.
This warning message is important for evaluation of nuclear data file.
However, this message is unnecessary for nuclear data processing code users.
The important warning message may not be found if the warning message of nuclear data file is output.
////////////////////////////////////////////////////////////////////////////////////////////////////
2020/06/18 (Version 1.02.014 -> 1.02.015)
The old version considered that the unit of a of Watt spectrum (MF=5, LF=11) is not concerned to energy.
So, the old version multiplies 1.0E+6 when the unit of energy is changed from eV to MeV.
However, the unit of this value is energy and this value must be multiply by 1.0E-6 ehen the unit of energy is changed from eV to MeV.
The new version is modified the unit conversion of a of Watt spectrum.
The new functions, i.e., devide_full_path, get_file_name, get_path_name, and get_suffix_name, are added.
These functions are used to get file name, path name, and suffix name from full path name.
Some bugs to modify probability table are modified.
This class automatically set the output ACE file name using the original ACE file name.
If the original ACE file name is “../ACE/xxx.ace”, the output ACE file name becomes “0001/../ACE/xxx.ace”.
In this case, this tool cannot write the output ACE file if “0001/../ACE” directory cannot be found.
The new version remove path name using new function of FileCommentRemover class (get_file_name function).
The output ACE file name using new version is “0001/xxx.ace”.
////////////////////////////////////////////////////////////////////////////////////////////////////
2020/06/17 (Version 1.02.013 -> 1.02.014)
To remove the minus residual cross section, the residual cross section is modified when residual cross section is less than 1.0E-5.
////////////////////////////////////////////////////////////////////////////////////////////////////
2020/06/12 (Version 1.02.012 -> 1.02.013)
The previous version of FRENDY sets initial secondary energy distribution for thermal scattering law data using beta value in evaluated nuclear data library.
If the distance of beta value is so narrow, the secondary energy distribution is also narrow and this narrow secondary energy distribution causes the error of MCNP.
To avoid this problem, the distance of secondary energy distribution is checked in ThermalScatterAceDataGenerator class.
This function is also added in ThermalScatterAceDataWriter, but now is commented out.
The previous version of pertubation tool cannot appropriately modify the cross section at the unresolved resonance region qith probability table if LSSF flag (self shielding flag) in MF=2 MT=151 is 0.
If LSSF is 1, the probability table is coefficient and the cross section is obtained for the product of probability table and cross section.
Since this tool modifies cross section, the cross section using probability table in the unresolved resonance region is also correctly modified.
To modify probability table when LSSF is 0, PerturbNuclearData class is modified.
The checker function (check_mt_list_all) for MF=03, MF=04, MF=05, MF=06, MF=09, and MF=10 is newly added.
If MF=04-06, 09, 10 data is found and MF=03 data is not found, FRENDY output warning message.
The checker function (check_energy_range) is newly added.
This function checks the overlap of resolved and unresolved resonance regions.
This class generates gas production cross section (MT=203-207).
The previous version output gas production cross section data even if all cross sections are zero.
To remove these zero cross section data, GasProductionXSCalculator class is modified.
*new
Evaluated nuclear data file format check mode is newly added in FRENDY.
This mode only read the evaluated nuclear data file and output warning message of nuclear data format.
////////////////////////////////////////////////////////////////////////////////////////////////////
2020/05/11 (Version 1.02.011 -> 1.02.012)
The remove_zero_data function in TabAdjuster class modifies tab1 data when all Y data is zero.
In such case, vector data is changed to X[0]=X_min, X[1]=X_max, Y[0]=0.0, Y[1]=0.0.
The old version considers that all Y data is zero when the element number of X data is zero.
The new version checks the element number of X data and Y value to correctly check the zero data.
////////////////////////////////////////////////////////////////////////////////////////////////////
2020/04/28 (Version 1.02.010 -> 1.02.011)
The old version cannot correctly calculate the 1st chance fission cross section (MT=19) of U232 from JENDL-4.0.
The old version check the cross section value and the 1st chance fission cross section is equal to the total fission cross section (MT=18) when the 1st chance fission cross section is less than 0.0 barn.
The back ground cross section of U232 is complex.
The old version misunderstand the upper energy region that changing from MT=19 to MT=18.
The new version changes the cross section from MT=19 to MT=18 where the 2nd chance fission cross section is less than 0.0 barn.
////////////////////////////////////////////////////////////////////////////////////////////////////
2020/04/24 (Version 1.02.009 -> 1.02.010)
Calculation of len2 value is modified to appropriately read MCNP.
////////////////////////////////////////////////////////////////////////////////////////////////////
2020/04/18 (Version 1.02.008 -> 1.02.009)
The old version cannot generate ACE file appropriately when secondary energy data is zero.
To avoid this probrem, checker method is added.
The bug is found in the automatic NJOY input maker.
In the old version, nmix in ACER is equak to natom in THERMR.
nmix in ACER is 1 without benzen.
////////////////////////////////////////////////////////////////////////////////////////////////////
2020/04/17 (Version 1.02.007 -> 1.02.008)
Typographical error is modified.
The cosine distribution is -1.0 - 1.0.
Cosine value of the old version becomes larger than 1.0 due to rounding error.
The new version modified cosine value if cosine value is less than -1.0 or larger than 1.0.
Calculation of len2 value is modified.
////////////////////////////////////////////////////////////////////////////////////////////////////
2020/04/16 (Version 1.02.006 -> 1.02.007)
The old version of FRENDY (and NJOY) uses emax_ace - 1.0E-5 as the top of energy.
FRENDY calculate double differential cross section at emax_tsl, emax_tsl - 1.0E-7, and emax_tsl + 1.0E-7.
In this case, emax_ace is equal to emax_tsl + 1.0E-7 and these three energy grid points (emax_tsl, emax_tsl - 1.0E-7, and emax_tsl + 1.0E-7) are removed to generate ACE file.
The new version of FERNDY treat these three energy grid points.
For NJOY users, emax_tsl - 1.0E-7 and emax_tsl + 1.0E-7 are changed to emax_tsl - 1.0E-5 and emax_tsl + 1.0E-5 to appropriately treat in ACER module.
The maximum thermal scattering law energy is changed from 4.0 eV to 10.0 eV to consider the thermal scattering law data in the wider energy region.
The old version of FRENDY modified cross section to 0.0 eV when the cross section is less than 0.0 barn without no warning message.
The new version of FRENDY output warning message to notice the users.
////////////////////////////////////////////////////////////////////////////////////////////////////
2020/04/07 (Version 1.02.005 -> 1.02.006)
The old version of FRENDY is changed interpolation scheme to linear-linear without linearization.
The new version linearizes Tab1 data befor normalization.
This modification affects ACE file neration.
The ENDF edit tool is newly developed to easily modify nuclear data.
This tool remove, the specified MF/MT data and change and add the specified MF/MT data from other nuclear data file.
The old version calculates double differential cross section (DDX) at the incident energy grid of total cross section (MF=3, MT=1).
The new version calculates DDX at incident energy grid of MF=3, MT=1 and NJOY's fixed energy grid (118 grid).
The top energy grid of old version is maximum energy of input data (EMAX).
The top energy grid of the incoherent energy grid is changed from EMAX to EMAX*(1.00001) to add 0 barn cross section data.
The minimum value is changed from 1.0E-30 to 1.0E-60 to treat thermal scattering law data.
NjoyInputReader class is modified to read NJOY's inpor format.
The warning message of nuclear data file is removed in the default option to emphasize the warning message of nuclear data processing.
This warning message is important for evaluation of nuclear data file.
However, this message is unnecessary for nuclear data processing code users.
The important warning message may not be found if the warning message of nuclear data file is output.
Timer tool of boost is changed from boost/timer.hpp to boost/timer/timer.hpp.
The class and function name to call time data are also changed.
////////////////////////////////////////////////////////////////////////////////////////////////////
2020/01/27 (Version 1.02.004 -> 1.02.005)
The new version calculate total partial production cross sections (MT=103-107) from MT=600-849.
////////////////////////////////////////////////////////////////////////////////////////////////////
2020/01/16 (Version 1.02.003 -> 1.02.004)
Pu-240 from ENDF/B-VIII.0 has MF=18 and MF=19 and cross section value of MF=19 in the resolved resonance region is 0.0 barn.
In this case, new version of FRENDY copy cross section value of MF=18 to that of MF=19.
If the cross section value of MF=19 is larger than 0.0 barn, FRENDY does not change the cross section value.
The minimum cross section value (min_sig_val at Config/CommonData.hpp) is changed from 1.0E-30 to 1.0E-40.
The old version modified minus cross section which is used for the back ground cross section to 0.0 barn.
The new version treat minus cross section.
If all cross section value is zero barn, the old version remove TAB1 data.
In such case, NJOY cannot treat the PENDF file.
The modified version outputs the cross section (0.0 barn) even if the all cross section value is 0.0 barn.
Error message in ErrorManager class is modified.
("Runtime error was occured." -> "Runtime error.")
Error message of set_photon_enegy_distr_by_ene_angle_distr_common_data function in FastAceDataGenerator class is modified to easiliy found the problem.
////////////////////////////////////////////////////////////////////////////////////////////////////
2019/11/22 (Version 1.02.002 -> 1.02.003)
The old version cannot treat "/" character in the comment line or tname(thermal zaid name).
If user want to set "o/lw" for the tname, FRENDY considers "o" and "/lw" is comment line.
To treat "/" character, NJOY input reader classes are modified.
To automatically calculate all thermal scattering law data in ENDF/B-VIII.0, ThermalScatterMatList class is modified.
////////////////////////////////////////////////////////////////////////////////////////////////////
2019/10/18 (Version 1.02.001 -> 1.02.002)
The old version generate ACE file with NJOY mode when calculation mode is not NJOY mode.
The cause of this problem is incorrect treatment of "#ifdef" flag in AceDataGenerator class.
AceDataGenerator class is modified process FRENDY mode.
////////////////////////////////////////////////////////////////////////////////////////////////////
2019/10/11 (Version 1.02.000 -> 1.02.001)
ACE file can not distinguish nu_prompt and nu_tot when nu_prompt or nu_tot are found.
The old version consideres that this value is nu_prompt.
The new version consideres that this value is nu_tot and outputs caution message.
////////////////////////////////////////////////////////////////////////////////////////////////////
2019/10/09 (Version 1.01.010 -> 1.02.000)
The default value of back ground cross section and read function of back ground cross section for probability table generation is modified.
The first background cross section is considered as infinite dilution cross section in the probability table generation.
The default value of back ground cross section is "1.0E-5, 1.0E-1, 1.0E+0, 1.0E+1, 3.0E+1, 1.0E+2, 3.0E+2, 1.0E+3, 1.0E+4, 1.0E+10".
In this case, FRENDY considers that the ininite dilution cross section is 1.0E-5 barn.
FRENDY is modified to sort the back ground cross section before the probability table calculation.
The probability bin setting function is modified.
The old version sometimes probability is 0.0 in some probability bins.
The cause of this probrems is incorrect probability bin.
The boundary of the probability bin is modified if the distance of probability bin is so narrow.
However, order of probability bin is not checked.
So, oreder of probability bin is incorrect in some cases.
To avoid this problem, the distance of probability bins is modified.
Adjustment amount of boundary of probability bin is also modified from 1.05 to 1.01.
GasProductionXSCalculater class is modified to correctly calcualte the gas production cross section.
The minimum value of resonance cross section of R-matrix limited formula is changed from min_value (1.0E-30) to 0.0.
Since material number of OinD2O from ENDF/B-VIII.0 and JEFF-3.3 is different to that of JENDL4.0.
FRENDY is modified to treat OinD2O from ENDF/B-VIII.0 and JEFF-3.3 in FRENDY original input format.
////////////////////////////////////////////////////////////////////////////////////////////////////
2019/08/19 (Version 1.01.007 -> 1.01.010)
The probability bin setting function is modified.
The old version sometimes probability is 0.0 in some probability bins.
To avoid this problem, the distance of probability bins is modified.
////////////////////////////////////////////////////////////////////////////////////////////////////
2019/08/13 (Version 1.01.005 -> 1.01.007)
(1) Bug fix of thermal quantities calculation
FRENDY automatically calculate thermal quantities when temperature is 293.6K.
The thermal quantities calculation requires fission and capture cross section at whole energy grid.
The fission cross section of Th-230 from JEFF-3.3 is threshold reaction. In such case, FRENDY cannot appropriately calculate the thermal quantities.
We modified FRENDY to skip then the fission or radiative capture cross section has threshold energy.
(2) Modification of algorithm for linearization of non-resonance cross section
If the energy grid is less than threshold energy, FRENDY slightly move the energy grid.
This algorithm requires long computation time when the difference of the threshold energy and the energy grid is so large.
We modified the algorithm.
The new algorithm changes the energy grid to threshold energy when the energy grid is smaller than the threshold energy.
(3) Change error message and processing rule
The old version of FRENDY stopped when the order of X data list in Tab1 record is not approrpate (X[i] < X[i-1]).
The modified version does not stop because some users do knot well about the nucler data file and they cannot modify the nucler data file by themselves.
The modified version outputs error message and removes this energy grid.
////////////////////////////////////////////////////////////////////////////////////////////////////
2019/08/10 (Version 1.01.005 -> 1.01.006)
The xsdir format is modified.
If the data size of the ACE file is so large, previous version cannot appropriately output xsdir.
////////////////////////////////////////////////////////////////////////////////////////////////////
2019/08/06 (Version 1.01.001 -> 1.01.005)
(1) Bug fix of total inelastic scattering cross section (MT=4)
When the total inelastic scattering cross section is not found in the ENDF file or the total inelastic scattering cross section is threshold reaction, FRENDY output inappropriate total inelastic scattering cross section.
We modified this problem.
(2) Treatment heat cross section in probability calculation
The previous version of FRENDY cannot treat the heat cross section since FRENDY has no function to calculate the heat cross section.
We modified to treat the heat cross section in probability calculation.
////////////////////////////////////////////////////////////////////////////////////////////////////
2019/07/08 (Version 1.00.005 -> 1.01.001)
(1) Bug fix
FRENDY modules are modified to appropriately process ENDF/B-VIII.0 and JEFF-3.3.
(2) Modification of origination of the include file name
The directory structure in the include file name is modified; The origination of the include file name is changed from current directory ("./") to the top directory of FRENDY ("frendy).
This modification is adopted to compile FRENDY using Visual Studio. Visual Studio users have to assign the source directory to compile the program. To compile the previous version (Version 1.00.005) using Visual Studio, users have to assign all directories in which the source files of FRENDY are contained. Users can compile the new version only by assigning the top directory.
This modification also affects the other compilers, e.g., GCC and Intel compiler. Users have to set -I option when they use these compilers.
(3) New tools using FRENDY modules
The make_perturbation_factor and perturbation_ace_file tools are newly added in "tools" directory. These tools are developed to perturb the ACE formatted files for the random sampling or the sensitivity analysis using continuous energy Monte Carlo calculation code.